Fuel canister and blockage pin fabrication for SLSF Experiment P4
Description
As part of its fast breeder reactor safety research program, Argonne National Laboratory (ANL) has conducted an experiment (SLSF Experiment P4) to determine the extent of fuel-failure propagation resulting from the release of molten fuel from one or more heat-generating fuel canisters. The test conditions consisted of 37 full-length FTR fuel pins operating at FTR rated core nominal peak fuel/reduced coolant conditions. Thirty-four of the the fuel pins were prototypical FTR mixed-oxide fuel pins. The other three fuel pins were fabricated with a mid-core section having an enlarged canister containing fully enriched UO2. Two of the canisters were cylindrical and one was fluted. The cylindrical canisters were designed to fail and release molten fuel into the 37-pin fuel cluster at near full power
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83017010.Files
15003040.pdf
Files
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- HEDL-SA--2855-S
Conference
- Title
- ANS annual meeting.
- Dates
- 12-17 Jun 1983.
- Place
- Detroit, MI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15003040
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FABRICATION; FFTF REACTOR; FUEL ASSEMBLIES; FUEL ELEMENT FAILURE; FUEL PELLETS; FUEL PINS; IRRADIATION CAPSULES; LMFBR TYPE REACTORS; PLUTONIUM DIOXIDE; REACTOR SAFETY; TESTING; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- CONF-830609--58.